ML20153B447
| ML20153B447 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/14/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20153B450 | List: |
| References | |
| DPR-66-A-121 NUDOCS 8803220148 | |
| Download: ML20153B447 (15) | |
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oq'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON D. C. 20555
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 License No. DPR-66 l
l 1.
The Nuclear Regulatory Comissinn Ithe Comission) has found that:
f A.
The application for amendment by Duquesne Light Company, et al.
l (the licensee) dated November 20, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFP Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance '(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health ar.d safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been catisfied.
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' 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.121, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ob F. Stolz, Directo r ject Directorate I-Division of teactor Pro,iects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14,1988
l
(
'Y ATTACHMENT TO LICENSE AMENDMENT N0.121 FACILITY OPERATING LICENSE NO DPR-66 DOCKET NO. 50-334 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 11-6 3/4 11-6 ~
3/4 11-8 3/4 11-8 3/4 11-9 3/4 11-10 3/4 11-10 3/4 11-11 3/4 11-11 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16 3/4 11-18 3/4 11-18 3/4 11-21 3/4 11-21 3/4 11-23 3/4 11-23 B3/4 11-3 B3/4 11-3 5-lb 5-lb 5-Ic
'N RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to MEMBER (S) OF THE PUBLIC from radioactive materials in liquid ef fluents released from the reactor unit (See Figure 5.1-2) shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
~
b.
During any calendar year to less than or equal to 3 arem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above
- limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a
Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the
- releases, and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.
(This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act).*
b.
The provisions of Specifications
- 3. 0. 3.
and 3.0.4 are not applicable.
- Applicable only if drinking water supply is taken from the receiving water body within 3 miles of.the plant discharge (3 miles downstream only).
l BEAVER VALLEY - UNIT 1 3/4 11-6 Amendment No.14.121
RADIOACTIVE EFFLUENTS LIOUID WASTE TREATMENT LIMITING CONDITION OF OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge when the projected doses due to liquid effluent releases from the reactor unit (See Figure 5.1-1) when averaged l
over-31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With liquid waste being discharged without treatment and exceeding the limits specified, prepare and submit to the commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for incperability.
2.
Action (s) taken to restore the inoperable equipment to operational status, and 3.
Summary description of action (s) taken to prevent a
recurrence, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 /sys, in accordance with the ODCM.
BEAVER VALLEY - UNIT 1 3/4 11-8 Anendment No. 'M.121 (Next page is 3/4 11-10)
i RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION g
3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be-limited to 1 10 curies, excluding tritium and dissolved or entrained noble gases.
a.
BR-TK-6A (Primary Water Storage Tank) b.
BR-TK-6B-(Primary Water Storage Tank) c.
LW-TK-7A (Steam Generator Drain Tank) d.
LW-TK-7B (Steam Generator Drain Tank) e.
Miscellaneous temporary outside radioactive liquid storage tanks.
APPLICABILITY:
At all times.
ACTION:
a.
With the quanti.ty of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and b.
Submit a Special Report to the Commission within 30 days pursuant to specification 6.9.2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits, c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4.1 The quantity of radioactive material contained in each of l
the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
BEAVER VALLEY - UNIT 1 3/4 11-10 Amendment No, h,121 l
J
4
- /
RADI' ACTIVE EFFLUENTS O
3/4.11.2 GASEOUS EFCLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate in the unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
a.
The dose rate limit for noble gases shall be 1 500 mrem /yr to the total body and 1 3000 mrem /yr to the skin *, and l
b.
The dose rate limit, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than 8
days shall be i 1500 mrem /yr to any organ.
APPLICABILITY:
At all tiates.
ACTION:
a.
With the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s), and b.
Submit a Special Report to the Commission within 30 days pursuant to specification 6.9.2.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQU'.REMENTS d.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM.
- During containment purge the dose rate may b~e averagid over 960 minutes.
BEAVER VALLEY - UNIT 1 3/4 11-11 Amendment No. M,121
A, TABLE 4.11-2
,e RADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Pt o,
Minimum
' lower Limit of
~
Sampling Analysis Type of Detection (LLD)
H g
Gaseous Release Type Frequency Frequency Activity Analysis (pC1/ml)*
8 A.
Waste Gas Storage P
P Principal Gamma Emitters 8 1 x 10-4 f
c Tank Each Tank Each Tank E
Grab Sample H-3 1 x 10-6 ct B.
Containment Purge P
P Principal Gamma Emitters 8 1 x 10-4 b
b Each Purge Each Purga 1 x 10-6 Grab Sample H-3 b
b M,c.e g
Principal Cm - Emitters 8 1 x 10-4 C.
Ventilation Systems 1.
Process Vent H-3 1 x 10-6 2.
Containment Vent 3.
Aux. Bldg. Vent w
N Continuousf d
I-131 1 x 10-12
^
W H
Charcoal Sample I-133 1 x 10-10 w
f Wd -
Principal Gamma EmittersE 1 x 10-11 Continuous Particulate (I-131, Others)
Sample Continuousf M
Gross alpha 1 x 10-11 Composite Particulate g
Sample Continuousf Q
Sr-89, Sr-90 1 x 10-Il g
Composite
<+
Particulate Sample z
f Noble Gas Noble Gases 1 x 10-6 g
Continuous Monitor Gross Beta and Gamma
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l
.3 RADIOACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose from the reactor unit in unrestricted areas l
(See figure 5.1.1) due to noble gases released in gaseous effluents shall be limited to the following:
l a.
During any calendar quarter to i 5 mrad for gamma radiation and i 10 mrad for beta radiation.
calendar year, to i 10 mrad for gamma radiation and 1 b.
During any 20 mrad for beta radiation.
APPLICABILITY:
At all times ACTION:
a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30
- days, pursuant to specification 6.9.2, a
Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to ba taken to assure the subsequent releases will be within the above limits.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations.
Cumulative dose contributions shall be l
determined in accordance with the ODCM at le,ast once every 31 days.
bet.VER VALLEY - UNIT 1 3/4 11-15 Amendment No. g,121 J
,,]
RADIOACTIVE EFFLUENTS'
- DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to MEMBER (s) OE.THE PUBLIC from radiciodines and radioactive materials in particulate form (excluding C-14),
and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the reactor unit ( See l
Figure 5.1-1) shall be limited to the following:
During any calendar quarter to 1 7.5 mrem to any organ, and a.
b.
During any calendar year to 1 15 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
I, a.
With the calculated dose from the release of radiciodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half lives greater than 8
- days, in gaseous effluents exceeding any of the above
- limits, prepare and submit to the commission within 30 days, pursuant to Specification 6.9.2, a
Special
- Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose calculations.
Cumulative dose contributions shall be I
determined in accordance with the ODCM at least once every 31 days, i
BEAVER VALLEY - UNIT 1 3/4 11-16 Amendment No. 34, 140, 121 (Next page is 3/4 11-18) i
', i RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION mm:
3.11.2.4 The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the reactor unit (see Figure 5.1-1), when aver-l aged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in geseous waste prior to their discharge when the projected doses due to gaseous effluent releases from l
the reactor unit (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to operational status, and 3.
Summary description of action (s) taken to prevent a
recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be l
projected at least once per 31 days, in accordance with the ODCM.
BEAVER VALLEY - UNIT 1 3/4 11-18 Amendment No M, W,121 (Next page is 3/4 11-20)
RADIOACTIVE EFFLUENTS
.f EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of oxygen in the waste gas holdup system shall be limited to 1
2%
by volume whenever the hydrogen concentration exceeds 4% by volume.
APPLICABILITY:
At all times.
ACTION:
a.
With the concentration of oxygen in the waste gas holdup system >
2%
by volume but 1
4%
by
- volume, immediately suspend all
[
additions of waste gases to the gaseous waste decay tank and i
reduce the concentration of oxygen to 1 2% by volume within 48 l
hours.
b.
With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 4%
by
- volume, immediately suspend all additions of waste I
to the affected tcnk and reduce the concentration o'f oxygen gases to less than or equal to 4% ty volume, then take ACTION a, above.
I c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6.1 The concentrations of oxygen in the waste gas holdup I
system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10 or monitoring in conjunction with its associated action statement.
BEAVER VALLEY - UNIT 1 3/4 11-21 Amendment No.M 121 1
RADIOACTIVE EFFLUENTS k
3/4.11.4 TOTAL DOSE t
I LIMITING CONDITION FOR OPERATION 3.11.4.1 The dose or dose commitment to MEMBER (S) OF THE PUBLIC from all facility releases is limited to 1 25 mrem to the total body or any organ (except the thyroid, which is limited to 1 75 mrem) for a
)
calendar year.
l APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, prepare and submit a
Special Report to the Commission within 30 days pursuant to specification 6.9.2 defining the corrective action and limit the subsequent releases such that the dose or dose commitment to MEMBER (S)
OF THE PUBLIC is limited to 1 25 mrem to the total body or any organ (except thyroid, which is limited to 1 75 mrem) for a calendar year.
This special report shall describe the steps to be taken or modifications necessary to prevent a recurrence.
Otherwise, obtain a
variance from the commission to permit releases which exceed the 40 CFR 190 Standard.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
(
SURVEILLANCE REQUIREMENTS l
l 4.11.4.1.1 Dose Calculations'.
Cummulative dose contributions from l
liquid and gaseous effluents shall be determined in accordance with Specification 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, and 3.11.2.3.b, and in accordance with the ODCM.
BEAVER VALLEY - UNIT 1 3/4 11-23 Amendment No. M,121 I
RADIOACTIVE EFFLUENTS BASES for unrestricted areas.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For individuals who may at times be within the site
- boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.
The specified release rate limits restrict, at all tires, the corresponding gamma and beta dose rates above background to an individual at.or beyond the exclusion area boundary to 1 500 mrem / year to the total body or to 1 3,000 mrem / year to the skin.
These release rate limits also
- restrict, at all
- times, the corresponding thyraid dose rate above background to a
child via the inhalation pathway to 1 1,500 l
mrem / year.
This specification applies to the release of gaseous effluents from Beaver Valley Power Station, Unit No. 1.
For units with shared radwaste treatment
- systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the
(
guides, set forth in section IV.A of Appendix I to assure that the l
releases of radioactive material in gaseous effluents will be kept l
"as low as is reasonably achievable".
The Surveillance Requirements implement the. requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially under-estimated.
The dose calculations establish 6d in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the I
methodology provided in Regulatory Guide 1.109, "Calculation of
(
Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatcry Guide 1.111, "Methods for Estimating Atmospheric BEAVER VALLEY - UNIT 1 B 3/4 11-3 Amendment No. 'M,121
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